科技报告详细信息
Fuel Temperature Coefficient of Reactivity | |
Loewe, W.E. | |
Savannah River Site (S.C.) | |
关键词: Temperature Coefficient; Control Elements; Measuring Methods; Reactivity; 22 General Studies Of Nuclear Reactors; | |
DOI : 10.2172/784244 RP-ID : DPSP-56-25-80 RP-ID : 784244 |
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美国|英语 | |
来源: UNT Digital Library | |
【 摘 要 】
A method for measuring the fuel temperature coefficient of reactivity in a heterogeneous nuclear reactor is presented. The method, which is used during normal operation, requires that calibrated control rods be oscillated in a special way at a high reactor power level. The value of the fuel temperature coefficient of reactivity is found from the measured flux responses to these oscillations. Application of the method in a Savannah River reactor charged with natural uranium is discussed.
【 预 览 】
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784244.pdf | 1093KB | download |